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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Apr 2025
Jan 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
April 2025
Latest News
Nuclear's future discussed at MURR expansion
ANS Executive Director/CEO Craig Piercy recently spoke on nuclear power’s potential for answering today’s energy demands as part of the Distinguished Lecture Series at the University of Missouri. He also took part in the ribbon cutting for a large addition to the University of Missouri Research Reactor (MURR).
Technical Session|Sponsored by Advanced/Novel Materials
Tuesday, December 12, 2023|3:10–4:50PM CST|Galerie 5
Session Chair:
Janelle P. Wharry (Purdue Univeristy)
Track Organizers:
Kevin Field (Univ. Michigan)
Benjamin Sutton (Electric Power Research Institute (EPRI))
Alternate Chair:
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Effects of Ti and Si Additions on Precipitate Number Density and Radiation Resistance of Additively Manufactured Oxide Dispersion Strengthened FeCrAl
3:10–3:30PM CST
T. Siggillino (Univ. Tennessee, Knoxville), T.C. Austin (Univ. Tennessee, Knoxville), S.J. Zinkle (Univ. Tennessee, Knoxville), C.P. Massey (ORNL)
Paper
Hydrogen Embrittlement of Zircaloy-4 Fabricated by Ultrasonic Additive Manufacturing
3:30–3:50PM CST
Y. Yan (ORNL), C.P. Massey (ORNL), B.E. Garrison (ORNL), S.A. Taller (ORNL), A.T. Nelson (ORNL)
Investigating the Structure-Property-Performance Relations of Cr Coatings for Zr Alloys
3:50–4:10PM CST
B.I. Aronson (Penn State), L.M. Erich (Penn State), M.J. Ammendola (Penn State), J. Hannon (Penn State), W.R. Tannehill (Penn State), M. Burton (Purdue), J.A. Reiss (Penn State), C.M. DeSalle (Penn State), P. Fourspring (Naval Nuclear Laboratory), B. Ensor (Naval Nuclear Laboratory), J. Clobes (Naval Nuclear Laboratory), K. Jenkins (Naval Nuclear Laboratory), D.E. Wolfe (Penn State)
Miniature Scale Creep Tests on Fuel Cladding Alloys Using a Novel Test System
4:10–4:30PM CST
L.M.A. Lima (NCSU), T. Hassan (NCSU), J. Eapen (NCSU), K.L. Murty (NCSU)
Effect of Neutron Irradiation and Heat Treatment on Hydrothermal and High-Temperature Corrosion Behavior of Additively Manufactured SiC Fibers
4:30–4:50PM CST
P. Cervenka (MIT), A. Seshadri (MIT), J. Pegna (Free Form Fiber), S. Harrison (Free Form Fiber), K. Shirvan (MIT)
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